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• Physical protection

  The Swedish Radiation Safety Authority imposes requirements for the physical protection of nuclear facilities and transports, for example protection against attacks and thefts of nuclear material. We monitor and check that the nuclear power industry complies with these requirements. We also help to ensure interaction between man, technology and organisation in a way so that physical...

  Content type: Regular Pages

• Decommissioning

  When the operator of a nuclear facility (i.e. the licence holder) is to decommission the facility, this must be done in a way that protects people and the environment from radioactivity in the facility. The Swedish Radiation Safety Authority issues regulations governing the planning and undertaking of dismantling activities; what’s more, the Authority performs checks to ensure that the...

  Content type: Regular Pages

• 2014:48 Technical Note, Independent assessment of groundwater sulphide content in the long-te

  Groundwater sulphide content is a key factor in the determination of canister lifetimes because of its role in corrosion of copper. SKB has based the canister lifetime analysis on a distribution of measured sulphide concentrations which are assumed to apply throughout the long-term analysis period. The distribution is based on expert judgement in the selection of samples that are regarded as...

  Content type: Publications

• 1992:3 Characterization of seismic ground motions for probabilistic safety analyses of nuclear facilities in Sweden. SUMMARY REPORT

  In Scandinavia seismic activity is generally low. Only a few incidents have been registered in historic time, which might have damaged an industrial plant of today. The risk of a nuclear accident in Sweden, caused by an earthquake, may thus be considered to be low. The two latest reactors Forsmark 3 and Oskarshamn 3 have been analysed and designed to resist a specified earthquake. For the...

  Content type: Publications

• 2017:19 Numerical simulations of headed anchors break in reinforced and non-reinforced concrete structures, Phase 2

  Background In the design of anchorage equipment in concrete structures the beneficial effects of reinforcement are, in most cases, not considered. The American ASCI 349-06 code opens up for a more detailed analysis where the beneficial impact of reinforcement on anchor capacity can be taken into account. How this analysis can be done is, however, not explicitly described in the code. The...

  Content type: Publications

• 2012:56 Technical Note, Biosphere Dose Assessment: Review of Dose Consequence of Radionuclides in the Uranium-238 Series Decay Chain

  As part of the Swedish Radiation Safety Authority (SSM) initial phase review of the Swedish Nuclear Fuel and Waste Management Company (SKB) SR-Site safety assessment for a spent nuclear fuel repository in Sweden, this technical note documents Center for Nuclear Waste Regulatory Analyses (CNWRAÒ) review of potential effects on SKB dose calculations from radioactive elements associated with...

  Content type: Publications

• 2007:21 On tentative decommissioning cost analysis with specific authentic cost calculations with the application of the Omega code on a case linked to the Intermediate storage facility for spent fuel in Sweden

  Marek Vasko, Vladimir Daniska, Frantisek Ondra, Peter Bezak, Kristina Kristofova, Peter Tatransky, Matej Zachar, Staffan Lindskog SKI English...

  Content type: Publications

• 2012:17 Technical Note, Corrosion of copper canister

  It is expected that the inflow of ground water to the deposition holes and tunnels in the Forsmark repository will be very slow. Thus, it might take some few hundred years up to thousand years before the deposition holes are filled with ground water and it might take 6000 years or more before the bentonite buffer is fully water saturated and pressurized. The copper canisters will therefore...

  Content type: Publications

• Fitness for work certificate – Work involving ionising radiation

  You need Adobe Acrobat Reader in order to read and fill out PDF forms. SSM Svenska You need Adobe Acrobat Reader in order to read and fill out PDF forms.

  Content type: Publications

• 2017:25 Evaluation of weld fatigue reduction in austenitic stainless steel pipe components

  Background The performed investigation is a continuation of the work performed in SSM 2015:38 where fatigue tests were performed on pressurized welded austenitic stainless steel piping components. The specimens were subjected to a realistic variable amplitude loading with mainly reversed bending deformation and particular focus on high cycle fatigue. The previous fatigue results were quite...

  Content type: Publications